RELAP/MOD3.2 Assessment Using an 11% Upper Plenum Break Experiment in the PSB Facility
The RELAP/MOD3.2 computer code has been assessed using an 11% upper plenum break experiment in the PSB test facility at the Electrogorsk Research and Engineering Center. This work was performed as part of the U.S. Department of Energy's International Nuclear Safety Program, and is part of the effort addressing the capability of the RELAP5/MOD3.2 code to model transients in Soviet-designed reactors. Designated VVER Standard Problem PSBV1, the test addressed several important phenomena related to VVER behavior that the code needs to simulate well. The code was judged to reasonably model the phenomena of two-phase flow natural circulation in the primary coolant system, asymmetric loop behavior, leak flow, loop seal clearance in the cold legs, heat transfer in a covered core, heat transfer in a partially covered core, pressurizer thermal-hydraulics, and integral system effects. The code was judged to be in minimal agreement with the experiment data for the mixture level and entrainment in the core, leading to a user recommendation to assess the sensitivity of transient calculations to the interphase drag modeling in the core. No judgments were made for the phenomena of phase separation without mixture level formation, mixture level and entrainment in the steam generators, pool formation in the upper plenum, or flow stratification in horizontal pipes because either the phenomenon did not occur in the test or there were insufficient measurements to characterize the behavior.
- Research Organization:
- Idaho National Lab. (INL), Idaho Falls, ID (United States); Pacific Northwest National Lab. (PNNL), Richland, WA (United States)
- Sponsoring Organization:
- USDOE Office of Nonproliferation and National Security (NN) (US)
- DOE Contract Number:
- AC07-99ID13727
- OSTI ID:
- 808522
- Report Number(s):
- INEEL/EXT-03-00058; TRN: US0302195
- Resource Relation:
- Other Information: PBD: 17 Jan 2003
- Country of Publication:
- United States
- Language:
- English
Similar Records
Analysis of the VVER Standard Problem INSC-PSBV1 '11% Coolant Leak from Upper Plenum' with RELAP5/MOD3.2
RELAP5/MOD3.2 Assessment Using INSC SP-PSBV1
Related Subjects
99 GENERAL AND MISCELLANEOUS//MATHEMATICS, COMPUTING, AND INFORMATION SCIENCE
CLEARANCE
COMPUTER CODES
COOLANTS
ENTRAINMENT
HEAT TRANSFER
MIXTURES
NATURAL CONVECTION
PRESSURIZERS
RADIATION PROTECTION
SIMULATION
STEAM GENERATORS
STRATIFICATION
TRANSIENTS
TWO-PHASE FLOW
RELAP/MOD3.2 CODE
LEAK FLOW